中温热管冷却堆的初步设计与中子分析

Sina Li, Binhuo Yan, Guojun Tang, Donghong Peng, Hongzhi Lu
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引用次数: 0

摘要

传统热管冷却堆具有堆芯温度高、燃料富集程度高的特点,其发展受到高温材料限制和低燃耗等不利因素的制约。本文针对高工作温度和高燃料富集的问题,提出了一种额定热功率为1.5MWt的新型热管冷却堆。低浓缩铀被用作燃料。采用汞热管代替传统的高温热管,以保持350℃左右的低工作温度。效率为33%的过热蒸汽/水循环可以保证反应器的高热效率。利用蒙特卡罗软件MCNP5分析了堆芯物理特性,包括控制棒值、中子能谱、中子分布、温度系数和堆芯寿命。带控制器的径向功率峰值系数为1.46,可满足传热要求。高控制棒值和高瞬态负温度系数也能保证该反应堆的高固有安全性。核心寿命约为8年。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Preliminary Design and Neutronics Analysis for a Medium Temperature Heat Pipe Cooled Reactor
Traditional heat pipe cooled reactors have the characteristics of high core temperature and high fuel enrichment, which makes its development limited by several unfavorable factors, such as the limitation of high temperature materials and low burnup, etc. In this paper, a new heat pipe cooled reactor with a rated thermal power of 1.5MWt is proposed to address the problems of high operating temperature and high fuel enrichment. Low-enriched uranium is used as fuel. Mercury heat pipe is used instead of the traditional high temperature heat pipe in order to maintain a low operating temperature of around 350 °C. A superheated steam/water cycle with an efficiency of 33% can ensure the high thermal efficiency of the reactor. The Monte Carlo software MCNP5 is used to analyze the core physics characteristics, including the control rod worth, neutron energy spectrum, neutron distribution, temperature coefficient and core lifetime. A radial power peaking factor of 1.46 with controls inserted can satisfy the heat transfer requirements. A high control rod worth and high transient negative temperature coefficient can also ensure a high inherent safety of this reactor. The core lifetime is around 8 years.
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